Book/Report

FZJ-2018-00333

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png Treatment of anisotropic neutron scattering in numerical reactor physics

Brockmann, H. (Corresponding author)FZJ*

1974
Kernforschungsanlage Jülich, Verlag Jülich

Please use a persistent id in citations: http://hdl.handle.net/2128/16499

Report No.: Juel-1147-RG

Abstract: In many problems of reactor physics anisotropic scattering of neutrons in the high energy range has an important influence on the neutron transport through matter. To take this fact into account in neutronic calculations computer codes based on the Monte Carlo method and on the method of diserete ordinates are used. The different techniques for the handling of anisotropic scattering in these transport codes are described and discussed. For a comparison of the different methods the neutron flux distribution in a simple assembly consisting of natural lithium is investigated by three computer codes : a modified version of the Monte Carlo code ESP, the discrete ordinates transport code ANISN, and the multigroup Monte Carlo code MORSE which uses the same group cross sections as ANISN. In general, the agreement between the different codes is good ; even better than one would expect from the approximations made in the codes ANISN and MORSE. Some discrepancies occur at the inner and outer boundary of the assembly ; but it cannot be concluded that these are due to an incorrect handling of anisotropic scattering in some of the codes.

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Contributing Institute(s):

1. Publikationen vor 2000 (PRE-2000)

Research Program(s):

1. 899 - ohne Topic (POF3-899) (POF3-899)

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Database coverage:

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